WO2023130356A1 - Pastille de combustible nucléaire atf à haute densité d'uranium et son procédé de préparation - Google Patents

Pastille de combustible nucléaire atf à haute densité d'uranium et son procédé de préparation Download PDF

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Publication number
WO2023130356A1
WO2023130356A1 PCT/CN2022/070727 CN2022070727W WO2023130356A1 WO 2023130356 A1 WO2023130356 A1 WO 2023130356A1 CN 2022070727 W CN2022070727 W CN 2022070727W WO 2023130356 A1 WO2023130356 A1 WO 2023130356A1
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WIPO (PCT)
Prior art keywords
nuclear fuel
atf
green body
density
water
Prior art date
Application number
PCT/CN2022/070727
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English (en)
Chinese (zh)
Inventor
陈明周
任啟森
廖业宏
王继伟
李雷
郭达禧
谢亦然
温建
李锐
葛洪恩
张显生
陈蒙腾
张永栋
Original Assignee
岭澳核电有限公司
中广核研究院有限公司
中国广核集团有限公司
中国广核电力股份有限公司
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Application filed by 岭澳核电有限公司, 中广核研究院有限公司, 中国广核集团有限公司, 中国广核电力股份有限公司 filed Critical 岭澳核电有限公司
Priority to EP22917828.0A priority Critical patent/EP4293686A4/fr
Priority to PCT/CN2022/070727 priority patent/WO2023130356A1/fr
Priority to CN202280007106.7A priority patent/CN116711026A/zh
Publication of WO2023130356A1 publication Critical patent/WO2023130356A1/fr

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/045—Pellets
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
    • G21C21/10—Manufacture of fuel elements or breeder elements contained in non-active casings by extrusion, drawing, or stretching by rolling, e.g. "picture frame" technique
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/16—Details of the construction within the casing
    • G21C3/20—Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/62—Ceramic fuel
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the invention relates to the technical field of nuclear fuel, in particular to a high uranium density ATF nuclear fuel pellet and a preparation method thereof.
  • Uranium oxide ceramic fuel has the advantages of high melting point, low radiation swelling, mature preparation technology, low cost, good compatibility with zirconium alloy cladding materials, and is an ideal nuclear reactor fuel.
  • the vast majority of PWR nuclear power fuels use UO 2 pellets.
  • the thermal conductivity of UO2 is low and the fuel rod temperature gradient is large, affecting the increase of fuel element burnup. Under deep burnup, the release rate of pellet fission gas increases, and the risk of mechanical physical and chemical reactions of fuel rods (referred to as PCI effect) increases.
  • ATF Accident Tolerant Fuel
  • Uranium carbides, nitrides and silicides are covalent bond compounds formed by metal uranium elements and non-metal elements, and have the properties of both metals and ceramics.
  • the non-metallic elements C, N, and Si in the above compounds have small atomic weights and small neutron absorption cross-sections, and are important research objects for ATF fuels with high uranium density and high thermal conductivity.
  • uranium carbides, uranium nitrides, and uranium silicides have poor oxidation resistance and are easy to react with water and water vapor, resulting in the loss of integrity of the pellets, so they cannot be directly used as pellet materials for water-cooled nuclear reactors.
  • the technical problem to be solved by the present invention is to provide a high-uranium-density ATF nuclear fuel pellet suitable for water-cooled nuclear reactors and a preparation method thereof.
  • the technical solution adopted by the present invention to solve the technical problems is: provide a high uranium density ATF nuclear fuel pellet, comprising a columnar inner area, an isolation layer coated on the outer surface of the inner area, and an isolation layer coated on the outer surface of the inner area. Peripheral area outside the layer;
  • the inner zone is made of nuclear fuel resistant to water and water vapor oxidation and high uranium density nuclear fuel; the outer zone is made of nuclear fuel resistant to water and water vapor oxidation;
  • the mass of the high-uranium-density nuclear fuel accounts for 3% to 50% of the total mass of the inner region and the isolation layer.
  • the nuclear fuel resistant to water and water vapor oxidation includes at least one of UO 2 , PuO 2 , and a mixture of UO 2 and ThO 2 .
  • the high-uranium-density nuclear fuel includes at least one of UN, UC, PuN, ThN, and U 3 Si 2 .
  • the grain size of the high uranium density nuclear fuel is smaller than the grain size of the water and water vapor oxidation resistant nuclear fuel.
  • the grain size of the high-uranium-density nuclear fuel is 0.8 times or less than the grain size of the water and water vapor oxidation-resistant nuclear fuel.
  • the peripheral zone includes a cylinder surrounding the inner zone, two end caps connected to opposite ends of the cylinder and covering opposite ends of the inner zone.
  • the thickness of the peripheral region is ⁇ 1/3 of the radius of the high uranium density ATF nuclear fuel pellet.
  • the isolation layer is made of metal, metal oxide or metal nitride.
  • the metal includes at least one of Cr and Al; the metal oxide includes at least one of Cr 2 O 3 and Al 2 O 3 ; the metal nitride includes CrN, ZrN, AlN and Cr 2 N at least one.
  • the surface of the high-uranium-density nuclear fuel is coated with an anti-oxidation protective layer.
  • the anti-oxidation protective layer is made of at least one of Cr 2 O 3 and Al 2 O 3 ; or, the anti-oxidation protective layer is made of Nb, Cr, Al, W, Mo, CrN, ZrN, AlN and at least one of Cr 2 N.
  • the present invention also provides a method for preparing high uranium density ATF nuclear fuel pellets, comprising the following steps:
  • the nuclear fuel resistant to water and water vapor oxidation is mixed with the high uranium density nuclear fuel and pressed into a columnar body, and the nuclear fuel resistant to water and water vapor oxidation is pressed into a peripheral green body;
  • the peripheral blank includes two cylindrical blanks; one end of each cylindrical blank is open and the other end is closed;
  • step S3 the cylindrical green body is loaded into one of the cylindrical green bodies, and then the other cylindrical green body is butted onto the previous cylindrical green body to form a peripheral green body and the The cylindrical blanks are enclosed therein; or, two cylindrical blanks are relatively sleeved on the cylindrical blanks and butted to form peripheral blanks, and the cylindrical blanks are enclosed therein.
  • the peripheral blank includes a cylindrical blank with one end open and an end cap blank;
  • step S3 the cylindrical green body is loaded into the cylindrical green body, and then the end cap green body is fitted to the open end of the cylindrical green body and covered on the cylindrical green body, and The columnar blank is enclosed in the cylindrical blank.
  • the sintering temperature is 1000°C-2000°C; the sintering pressure is 40MPa-150MPa.
  • step S4 the densification sintering adopts a field-assisted sintering process, and the sintering temperature is 1500°C-1900°C.
  • step S1 the surface of the high-uranium-density nuclear fuel is coated with an anti-oxidation protective layer.
  • the present invention also provides another method for preparing high uranium density ATF nuclear fuel pellets, comprising the following steps:
  • the peripheral blank includes a cylindrical blank with one end open and an end cap blank; in step S2, insulating materials are respectively arranged on the inner surface of the cylindrical blank and the end cap Separate layers are formed on one surface of the
  • step S2 the nuclear fuel resistant to water and water vapor oxidation is mixed with the high-uranium density nuclear fuel and loaded into the cylindrical blank, and then the end cap blank is fitted to the open end of the cylindrical blank .
  • the sintering temperature is 1000°C-2000°C; the sintering pressure is 40MPa-150MPa.
  • step S4 the densification sintering adopts a field-assisted sintering process, and the sintering temperature is 1500°C-1900°C.
  • step S1 the surface of the high-uranium-density nuclear fuel is coated with an anti-oxidation protective layer.
  • the present invention also provides another method for preparing high uranium density ATF nuclear fuel pellets, comprising the following steps:
  • the nuclear fuel resistant to water and water vapor oxidation is mixed with the high-uranium density nuclear fuel and then pressed into a columnar green body;
  • the sintering temperature is 1000°C-2000°C; the sintering pressure is 40MPa-150MPa.
  • step S4 the densification sintering adopts a field-assisted sintering process, and the sintering temperature is 1500°C-1900°C.
  • step S1 the surface of the high-uranium-density nuclear fuel is coated with an anti-oxidation protective layer.
  • the high uranium density ATF nuclear fuel pellet of the present invention arranges the high uranium density nuclear fuel inside the pellet, increases the uranium load of the pellet, effectively reduces the central temperature of the pellet, and then improves the economy and safety of the reactor operation; and,
  • the isolation layer and the peripheral area wrap the inner area containing the high-uranium-density nuclear fuel in turn to form a double effective anti-oxidation shielding layer, which prevents the high-uranium-density nuclear fuel from reacting with external water or water vapor, and improves the overall anti-oxidation of the pellet It can realize the application of high uranium density nuclear fuel pellets in water-cooled nuclear reactors, and improve the accident tolerance of nuclear reactors.
  • Fig. 1 is the transverse cross-sectional structure schematic diagram of the high uranium density ATF nuclear fuel pellet of an embodiment of the present invention
  • Fig. 2 is a schematic view of the vertical cross-sectional structure of a high uranium density ATF nuclear fuel pellet according to an embodiment of the present invention.
  • the high uranium density ATF nuclear fuel pellet of the present invention includes a columnar inner region 10, an isolation layer 20 coated on the outer surface of the inner region 10, and an isolation layer 20 and an inner region 10 coated on the outer surface of the inner region 10. outside the peripheral area 30 .
  • the peripheral area 30 , the isolation layer 20 and the inner area 10 are three composite fuel pellets connected as one.
  • the inner zone 10 is made of nuclear fuel resistant to water and water vapor oxidation and high uranium density nuclear fuel.
  • the nuclear fuel resistant to water and water vapor oxidation includes a mixture of UO 2 and ThO 2 , at least one of UO 2 and PuO 2 , that is, it may include a mixture of UO 2 and ThO 2 , or include UO 2 , or include PuO 2 , or include Or include two or more of the aforementioned three.
  • the high-uranium-density nuclear fuel includes at least one of UN, UC, PuN, ThN, and U 3 Si 2 .
  • the nuclear fuel with high uranium density is preferably at least one of UC and U 3 Si 2 .
  • the peripheral area 30 is made of nuclear fuel resistant to water and water vapor oxidation, and the nuclear fuel resistant to water and water vapor oxidation in the peripheral area 30 includes at least one of UO 2 , PuO 2 , and a mixture of UO 2 and ThO 2 , that is, it may include
  • the mixture of UO 2 and ThO 2 either includes UO 2 , or PuO 2 , or includes two or more of the aforementioned three.
  • the water and water vapor oxidation-resistant nuclear fuel in the peripheral zone 30 and the water and water vapor oxidation-resistant nuclear fuel in the inner zone 10 can choose the same oxide, or different oxides, which can be flexibly selected according to actual needs.
  • the mass of the high-uranium-density nuclear fuel accounts for 3%-50% of the total mass of the inner region 10 and the isolation layer 20, preferably less than 50%.
  • the isolation layer 20 is located between the peripheral region 30 and the inner region 10 , and forms a double anti-oxidation shielding layer with the peripheral region 30 to protect the inner region 10 .
  • the isolation layer 20 can be made of metal, such as at least one of Cr and Al; or, it can be made of metal oxide, such as at least one of Cr 2 O 3 and Al 2 O 3 ; or, it can be made of metal nitride, Such as at least one of CrN, ZrN, AlN and Cr 2 N. Among them, the metal nitride can react with water or water vapor to form an oxide layer, so as to achieve anti-oxidation protection.
  • the thickness of the isolation layer 20 is less than 1 mm, preferably 30 ⁇ m-100 ⁇ m.
  • the existence of the isolation zone 20 effectively prevents water and water vapor from entering the internal zone 10 through cracks, thereby avoiding the UN and high temperature existing in the internal zone 10 The water or water vapor reacts to cause crushing and destruction of the inner region 10 .
  • the high-uranium density nuclear fuel and the anti-water and water vapor oxidation-resistant nuclear fuel are mixed to form the inner zone 10, and the anti-oxidation
  • the peripheral area 30 and the isolation layer 20 made of nuclear fuel oxidized by water and water vapor are wrapped in the outer side of the entire inner area 10 in turn, and the inner area 10 is used as the inner core part of the entire nuclear fuel pellet, so that the inner area 10 where the high-uranium density nuclear fuel is located
  • Directional dispersion is inside the nuclear fuel pellets, isolating the high uranium density nuclear fuel from the external water or water vapor, so as to avoid or slow down the contact and reaction between the high uranium density nuclear fuel and the external water or water vapor.
  • the particle size of the high-uranium-density nuclear fuel is smaller than that of the anti-water and water vapor oxidation-resistant nuclear fuel, so that the anti-water and water vapor oxidation-resistant nuclear fuel can wrap the high-uranium density nuclear fuel to form an effective anti-oxidation shielding layer .
  • the particle size of the nuclear fuel with high uranium density is 0.8 times or less, more preferably 0.1 times or less than the particle size of the nuclear fuel resistant to water and water vapor oxidation.
  • the surface of the high-uranium-density nuclear fuel can also be coated with an anti-oxidation protective layer to improve the isolation effect of the high-uranium-density nuclear fuel from water or water vapor.
  • the anti-oxidation protective layer is made of at least one of Cr 2 O 3 and Al 2 O 3 ; or, the anti-oxidation protective layer is made of Nb, Cr, Al, W, Mo, CrN, ZrN, AlN and Cr 2 N At least one of these components is capable of reacting with water or water vapor to form an oxide layer.
  • the thickness of the material of the anti-oxidation protective layer is preferably micron or submicron.
  • the inner region 10 is a columnar structure, preferably a cylinder.
  • the peripheral area 30 wraps the entire inner area 10, including the side faces and end faces of the inner area 10. Therefore, as shown in FIG.
  • the barrel 31 has opposite ends and covers two end caps 32 on opposite ends of the inner region 10 .
  • the isolation layer 20 is disposed corresponding to the outer structure of the inner region 10 or the inner structure of the peripheral region 30 to connect between the inner region 10 and the peripheral region 30 .
  • the inner region 10 where the high uranium density nuclear fuel is located occupies the main body of the entire nuclear fuel pellet, so the peripheral region 30 is smaller than the inner region 10 in terms of volume and thickness set up.
  • the thickness of the peripheral zone 30 is ⁇ 1/3 of the radius of the high uranium density ATF nuclear fuel pellet.
  • the preparation of the high-uranium-density ATF nuclear fuel pellets of the present invention is mainly formed by high-density sintering, and the overall average density reaches more than 95% of the theoretical density (>95% TD).
  • the nuclear fuel resistant to water and water vapor oxidation is mixed with the high uranium density nuclear fuel and pressed into a columnar green body, and the nuclear fuel resistant to water and water vapor oxidation is pressed into a peripheral green body.
  • the above two powders are mixed evenly and placed in corresponding molds, and pressed into a columnar green body by cold isostatic pressing.
  • the surface of high uranium density nuclear fuel can be selectively coated with an anti-oxidation protective layer.
  • the water and water vapor oxidation-resistant nuclear fuel powder of the peripheral body can be selected from the same type of water and water vapor oxidation-resistant nuclear fuel powder as the columnar body, and the particle size is also larger than that of the high-uranium-density nuclear fuel powder.
  • the nuclear fuel powder resistant to water and water vapor oxidation is placed in a mold, and is pressed into two cylindrical green bodies by cold isostatic pressing, one end of each cylindrical green body is open and the opposite end is closed; or, using The cold isostatic pressing method forms a cylindrical green body and an end cap green body, one end of the cylindrical green body is open and the other end is closed; the end cap green body is matched with the open end of the cylindrical green body.
  • the isolation material is made of metal, metal oxide or metal nitride.
  • the metal includes at least one of Cr and Al; the metal oxide includes at least one of Cr 2 O 3 and Al 2 O 3 ; the metal nitride includes at least one of CrN, ZrN, AlN and Cr 2 N.
  • the isolation material is formed on all the outer surfaces of the columnar body by sputtering or spraying.
  • two cylindrical blanks are included corresponding to the above-mentioned peripheral blanks.
  • step S3 put the cylindrical blank into one cylindrical blank, and then connect the other cylindrical blank to the previous tube
  • two cylindrical green bodies are docked to form a peripheral green body and the cylindrical green body is enclosed; or, two cylindrical green bodies are relatively sleeved on the cylindrical green body and butted to form a peripheral green body, The columnar green body is enclosed therein.
  • peripheral blank in another embodiment, corresponding to the above-mentioned peripheral blank, it includes a cylindrical blank and an end cap blank.
  • step S3 put the cylindrical blank into the cylindrical blank, and then fit the end cover blank to the cylinder The open end of the cylindrical green body is covered on the cylindrical green body, and the cylindrical green body is enclosed in the cylindrical green body.
  • the sintering temperature is 1000°C-2000°C; the sintering pressure is 40MPa-150MPa.
  • a carbon-free mold is used to place the peripheral green body and the cylindrical green body during sintering.
  • the temperature increase rate is controlled to be no higher than 30° C./min, so as to ensure the density between the formed peripheral region 30 , isolation layer 20 and inner region 10 and reduce the Density difference between the three.
  • the sintering temperature is 1600°C-2000°C, and the temperature is kept for more than 3 hours after reaching the required sintering temperature.
  • the sintering temperature is 1500°C-1900°C, and the temperature is kept for ⁇ 60 minutes after reaching the required sintering temperature.
  • a spark plasma sintering (SPS) process using pulsed current or a current-activated hot-pressing sintering process using direct current can be used.
  • SPS spark plasma sintering
  • the field-assisted sintering process can realize the rapid prototyping of nuclear fuel pellets, and the density is high, reaching more than 95% of the theoretical density.
  • a power supply system is also added to conduct electric heating on the carbon-free mold where the peripheral green body and the cylindrical green body are placed, so as to perform auxiliary heating of the cylindrical green body and the peripheral green body in the radial direction;
  • the alternating magnetic field generated by the coil of the power supply system disturbs the heating current of the field-assisted sintering, so as to form multi-directional heating directions for the columnar green body and the peripheral green body.
  • the peripheral green body is preferably formed by cold isostatic pressing.
  • the peripheral blank includes a cylindrical blank and an end cap blank; one end of the cylindrical blank is open and the other end is closed; the end cover blank is adapted to the open end of the cylindrical blank .
  • the peripheral blank comprises a cylindrical blank; one end of the cylindrical blank is open and the other end is closed.
  • the isolation material is made of metal, metal oxide or metal nitride.
  • the metal includes at least one of Cr and Al; the metal oxide includes at least one of Cr 2 O 3 and Al 2 O 3 ; the metal nitride includes at least one of CrN, ZrN, AlN and Cr 2 N.
  • the isolation material is formed on all inner surfaces of the peripheral body by sputtering or spraying, including the inner surface of the cylindrical body and one surface of the end cap body.
  • the nuclear fuel resistant to oxidation by water and water vapor is mixed with the high-uranium-density nuclear fuel and loaded into the peripheral green body with the isolation layer 20 .
  • the surface of high uranium density nuclear fuel can be selectively coated with an anti-oxidation protective layer.
  • step S3 the specific operation of step S3 is as follows: mix the nuclear fuel resistant to water and water vapor oxidation with the high uranium density nuclear fuel and put them into the cylindrical green body, and then put the end cover
  • the cap blank fits onto the open end of the cylindrical blank, enclosing the cylindrical blank within the cylindrical blank.
  • step S3 the specific operation of step S3 is as follows: put the cylindrical green body into the mold, mix the nuclear fuel resistant to water and water vapor oxidation with the high uranium density nuclear fuel, and load the cylindrical green body In the body, the nuclear fuel resistant to water and water vapor oxidation is covered on the open end of the cylindrical green body, and the cylindrical green body is sealed to form a complete peripheral green body with the cylindrical green body. After subsequent densification and sintering, the water and water vapor oxidation resistant nuclear fuel covering the open end of the cylindrical body forms an end cap, joining the cylindrical body as a peripheral zone 30 .
  • the sintering temperature is 1000°C-2000°C; the sintering pressure is 40MPa-150MPa.
  • a carbon-free mold is used to place the peripheral green body and the cylindrical green body during sintering.
  • the temperature increase rate is controlled to be no higher than 30° C./min, so as to ensure the density between the formed peripheral region 30 , isolation layer 20 and inner region 10 and reduce the Density difference between the three.
  • the sintering temperature is 1600°C-2000°C, and the temperature is kept for more than 3 hours after reaching the required sintering temperature.
  • the sintering temperature is 1500°C-1900°C, and the temperature is kept for ⁇ 60 minutes after reaching the required sintering temperature.
  • a spark plasma sintering (SPS) process using pulsed current or a current-activated hot-pressing sintering process using direct current can be used.
  • SPS spark plasma sintering
  • the field-assisted sintering process can realize the rapid prototyping of nuclear fuel pellets, and the density is high, reaching more than 95% of the theoretical density.
  • a power supply system is also added to conduct electric heating on the carbon-free mold where the peripheral green body and the cylindrical green body are placed, so as to perform auxiliary heating of the cylindrical green body and the peripheral green body in the radial direction;
  • the alternating magnetic field generated by the coil of the power supply system disturbs the heating current of the field-assisted sintering, so as to form multi-directional heating directions for the columnar green body and the peripheral green body.
  • the nuclear fuel resistant to water and water vapor oxidation is mixed with the high-uranium-density nuclear fuel, and then pressed into a columnar green body.
  • the above two powders are mixed evenly and placed in corresponding molds, and pressed into a columnar green body by cold isostatic pressing.
  • the isolation material is made of metal, metal oxide or metal nitride.
  • the metal includes at least one of Cr and Al; the metal oxide includes at least one of Cr 2 O 3 and Al 2 O 3 ; the metal nitride includes at least one of CrN, ZrN, AlN and Cr 2 N.
  • the isolation material is formed on all the outer surfaces of the columnar body by sputtering or spraying.
  • the water and water vapor oxidation-resistant nuclear fuel of the peripheral body can be selected from the same type of water and water vapor oxidation-resistant nuclear fuel as the columnar body, and the particle size is also larger than that of the high-uranium-density nuclear fuel powder.
  • the sintering temperature is 1000°C-2000°C; the sintering pressure is 40MPa-150MPa.
  • a carbon-free mold is used to place the peripheral green body and the cylindrical green body during sintering.
  • the temperature increase rate is controlled to be no higher than 30° C./min, so as to ensure the density between the formed peripheral region 30 , isolation layer 20 and inner region 10 and reduce the Density difference between the three.
  • the sintering temperature is 1600°C-2000°C, and the temperature is kept for more than 3 hours after reaching the required sintering temperature.
  • the sintering temperature is 1500°C-1900°C, and the temperature is kept for ⁇ 60 minutes after reaching the required sintering temperature.
  • a spark plasma sintering (SPS) process using pulsed current or a current-activated hot-pressing sintering process using direct current can be used.
  • SPS spark plasma sintering
  • the field-assisted sintering process can realize the rapid prototyping of nuclear fuel pellets, and the density is high, reaching more than 95% of the theoretical density.
  • a power supply system is also added to conduct electric heating on the carbon-free mold where the peripheral green body and the cylindrical green body are placed, so as to perform auxiliary heating of the cylindrical green body and the peripheral green body in the radial direction;
  • the alternating magnetic field generated by the coil of the power supply system disturbs the heating current of the field-assisted sintering, so as to form multi-directional heating directions for the columnar green body and the peripheral green body.
  • the outer surface of the obtained high-uranium-density ATF nuclear fuel pellet can be processed, chamfered, etc. as required.

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  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
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  • Manufacturing & Machinery (AREA)
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Abstract

La présente invention concerne une pastille de combustible nucléaire ATF à haute densité d'uranium et son procédé de préparation. La pastille de combustible nucléaire ATF à haute densité d'uranium comprend une région interne en forme de colonne (10), une couche d'isolation (20) recouvrant la surface externe de la région interne (10), et une région périphérique (30) recouvrant la couche d'isolation (20), la région interne (10) étant préparée à partir d'un combustible nucléaire résistant à l'oxydation de l'eau et de la vapeur d'eau, et d'un combustible nucléaire à haute densité d'uranium ; la région périphérique (30) étant préparée à partir d'un combustible nucléaire résistant à l'oxydation de l'eau et de la vapeur d'eau ; et la masse du combustible nucléaire à haute densité d'uranium représentant 3 à 50 % de la masse totale de la région interne (10) et de la couche d'isolation (20). La pastille de combustible nucléaire ATF à haute densité d'uranium présente une quantité accrue de charge d'uranium et une température centrale effectivement réduite, ce qui améliore l'efficacité économique et la sécurité du fonctionnement d'un réacteur ; l'utilisation du combustible nucléaire à haute densité d'uranium dans un réacteur nucléaire refroidi à l'eau est réalisée, et la capacité de tolérance aux accidents du réacteur nucléaire est améliorée.
PCT/CN2022/070727 2022-01-07 2022-01-07 Pastille de combustible nucléaire atf à haute densité d'uranium et son procédé de préparation WO2023130356A1 (fr)

Priority Applications (3)

Application Number Priority Date Filing Date Title
EP22917828.0A EP4293686A4 (fr) 2022-01-07 2022-01-07 Pastille de combustible nucléaire atf à haute densité d'uranium et son procédé de préparation
PCT/CN2022/070727 WO2023130356A1 (fr) 2022-01-07 2022-01-07 Pastille de combustible nucléaire atf à haute densité d'uranium et son procédé de préparation
CN202280007106.7A CN116711026A (zh) 2022-01-07 2022-01-07 高铀密度atf核燃料芯块及其制备方法

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Application Number Priority Date Filing Date Title
PCT/CN2022/070727 WO2023130356A1 (fr) 2022-01-07 2022-01-07 Pastille de combustible nucléaire atf à haute densité d'uranium et son procédé de préparation

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